Measurement and Estimation of Cross Sections for 55Mn(n, γ)56Mn and 65Cu(n, γ)66Cu Reactions Using Accelerator-Based Neutron Source

Barough, Mehdi Salehi; Bharud, V. D.; Patil, B.J.; Attar, F.M.D.; Bhoraskar, V.N.; Dhole, S.D.

doi:10.1080/00295639.2017.1323505

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2023

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“…55 Mn is used as an alloy of structural material in which accurate capture cross-section is necessary for the future of reactors. Reliable estimation of the activation levels of manganese is needed to support critical safety analyses (Barough et al 2017). In nuclear data evaluations, theoretical calculation is essential and the evaluated data from the theoretical calculation play an important role on their applications to fusion reactor neutronics.…”

Section: Introductionmentioning

confidence: 99%

NEUTRON INDUCED 55Mn REACTION IN THE ENERGY RANGE 0.001 MeV TO 40 MeV

Rahman,

Happy,

Ovi

et al. 2023

MJS

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Neutron induced 55Mn reactions are evaluated in the energy range 0.001 MeV to 40 MeV using TALYS 1.95 computer code. During this evaluation, local and global parameterisations of Koning and Delaroche are used in nuclear optical model. Comparisons were made with experimental data, collected from EXFOR and other sources. Some optical model parameters (OMP) were needed to be adjusted for better agreement between theoretical calculations and experimental findings. Various evaluated libraries such as ENDF, JENDL etc. are being checked and compared with our evaluation. TALYS evaluation shows better agreement when parameters were adjusted.

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Section: Introductionmentioning

confidence: 99%